This report evaluates the performance of the vital MG sets during a worst case load transfer. Evaluation of test data showed: (1) The Vital MG Set withstood the extreme loading; (2) The load can be sustained well in excess of the required time limit; and (3) The transfer perturbation caused the frequency to exceed the limits set by the SDD. The follow up evaluations of the equipment powered by the MG sets demonstrated that the equipment function will not be degraded.

The Closed Loop In-Reactor Assembly (CLIRA) is a test vehicle for in-core material and fuel experiments in the Fast Flux Test Facility (FFTF). The FFTF is a fast flux nuclear test reactor operated for the Department of Energy (DOE) by Westinghouse Hanford Company in Richland, Washington. The CLIRA is a removable/replaceable part of the Closed Loop System (CLS) which is a sodium coolant system providing flow and temperature control independent of the reactor coolant system. The primary purpose of the CLIRA is to provide a test vehicle which will permit testing of nuclear fuels and materials at conditions more severe than exist in the FTR core, and to isolate these materials from the reactor core.

Preliminary fusion reactor designs have been developed based on the tandem mirror confinement concept. These have included a 1000 MWe fusion power reactor and a nearer term fusion-fission hybrid reactor with reduced plasma confinement and technology requirements. Brief descriptions are given.

The reactor design is a multicell arrangement wherein a series of field-reversed plasma layers are arranged along the axis of a long superconducting solenoid which provides the background magnetic field. Normal copper mirror coils and Ioffe bars placed at the first wall radius provide shallow axial and radial magnetic wells for each plasma layer. Each of 11 plasma layers requires the injection of 3.6 MW of 200 keV deuterium and tritium and produces 20 MW of fusion power. The reactor has a net electric output of 74 MWe and an estimated direct capital cost of $1200/kWe.

The simple mirror configuration, consisting of a long solenoid with increased field strength at the ends (magnetic mirrors), proved to be an unstable plasma container and was replaced by the minimum absolute value of B mirror configuration. The Yin-Yang minimum absolute value of B coil was chosen for the Mirror Fusion Test Facility (MFTF) experiment and recent conceptual designs of standard mirror reactors. For the multicell field-reversed mirror reactor concept we returned to the long solenoid configuration, augmented by normal copper mirror coils and Ioffe bars placed at the first wall radius to provide a shallow magnetic well for each field-reversed plasma layer. The central cell of the tandem mirror is also a long solenoid while the end plug cells require a minimum absolute value of B configuration.

For the past two years Alan Swain and Henry E. Guttmann, of the Statistics, Computing, and Human Factors Division, Sandia Laboratories, have been developing a handbook to aid qualified persons to evaluate the effect of human error on the availability of engineered safety systems and features in nuclear power plants. The handbook includes a mathematical model, procedures, derived human failure data, and principles of human behavior and ergonomics. The handbook is expanding the human error analyses which were presented in WASH--1400. The work, under the sponsorship of Probabilistic Analysis Staff, NRC Office of Nuclear Regulatory Research (Dr. M.C. Cullingford, NRC Program Manager), is about half completed. An outline of the handbook contents is given in copies of vugraphs (attached), followed by copies of human performance model abstractors (also attached). A first draft of the handbook is scheduled for NRC review by July 1, 1979.

Line 2''-IA-295-AB outside containment penetration S-2A was analyzed to ASME Section III, Subsection NC (Class 2) criteria. The line is part of the Containment Isolation System. The model considered the line from the penetration outward through the first isolation valve. Results of the analysis show that this section of the line meets Class 2 requirements without modification.

92,000 BeO--UO/sub 2/ fuel elements were fabricated for the upgrading of the Sandia Annular Core Pulse Reactor. The toxicity of BeO and the radioactivity of /sup 235/U necessitated special handling procedures and equipment. This document describes the materials, specifications, and fabrication process. (DLC)

A stress analysis was performed on the 2''-IA-299-AB pipe system inside containment penetration S-5B. Deadweight, thermal expansion and seismic loads were considered. The results indicate that this piping will meet ASME Section III, Class 2 requirements.